Plasma shape reconstruction is an important part of tokamak data analysis. An off-line plasma shape reconstruction, based on the EFIT code in Linux system, can be carried out in Q-shu Univ. Experiment in Steady-State Spherical Tokamak (QUEST). In this paper, the algorithm about equilibrium reconstruction is described in detail. Magnetic reconstruction in QUEST, which is calculated by the EFIT code according to the external magnetic measurements, is introduced and the results are presented in detail. It is known that the eddy current effect is large in QUEST experiment, the eddy current effect is first considered into equilibrium reconstruction. Fourier expansion is applied to reconstruct the vessel current distribution in EFIT code. To test the accuracy of the result, a comparison with the result of Cauchy condition surface method has made, which suggests the reliability of the result. A visualization interface is made, which is convenient for physicists and operators to analyze the behavior of plasma. At the same time, the operation space of elongated discharges is discussed based on the QUEST database. The real time EFIT will be applied to the plasma control system of QUEST in the future.

中文翻译：

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QUEST Tokamak 中的平衡重建和平衡特性

等离子体形状重建是托卡马克数据分析的重要组成部分。一种基于Linux系统EFIT代码的离线等离子体形状重建，可在Q-shu Univ进行。稳态球形托卡马克 (QUEST) 实验。在本文中，详细描述了关于平衡重建的算法。介绍了QUEST中的磁重建，它是根据外部磁测量通过EFIT代码计算得出的，并详细介绍了结果。众所周知，QUEST实验中涡流效应较大，平衡重建首先考虑涡流效应。傅里叶展开用于重建 EFIT 代码中的血管电流分布。为了检验结果的准确性，与柯西条件曲面法的结果进行了比较，这表明结果的可靠性。制作了可视化界面，方便物理学家和操作人员分析等离子体行为。同时，基于QUEST数据库讨论了拉长放电的操作空间。实时 EFIT 将在未来应用于 QUEST 的等离子控制系统。